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다지점 진동대를 이용한 원자력발전소 배관계통의 내진성능실험

Seismic Capacity Test of Nuclear Piping System using Multi-platform Shake Table

  • 정진환 (부산대학교 사회환경시스템공학부) ;
  • 계만수 (MIDAS IT 중국지사) ;
  • 서영득 (부산대학교 사회환경시스템공학부) ;
  • 최형석 (부산대학교 지진방재연구센터) ;
  • 김민규 (한국원자력연구원)
  • 투고 : 2012.07.13
  • 심사 : 2012.12.20
  • 발행 : 2013.01.02

초록

In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress (138 MPa) of the piping system even under the maximum excitation level of this test.

키워드

참고문헌

  1. Machida H, Yoshimura S. Probabilistic fracture mechanics analysis of nuclear piping considering variation of seismic loading. International Journal of Pressure Vessels and Piping. 2002;79(3):193-202. https://doi.org/10.1016/S0308-0161(02)00011-X
  2. Keowen RS, Laske A, Johnson, Merz KL. Differences in dynamic response of typical class II piping due to restraint method and input amplitude. Nuclear Engineering and Design. 1988;107:215-226. https://doi.org/10.1016/0029-5493(88)90324-X
  3. Touboul F, Sollogoub P, Blay N. Seismic behaviour of piping systems with and without detect : experimental and numerical evaluations. Nuclear Engineering and Design. 1999;192:243-260. https://doi.org/10.1016/S0029-5493(99)00111-9
  4. Zhang T, Brust FW, Shim DJ, Wikowski G, Nie J, Hofmayer C. Analysis of JNES Seismic Tests on Degraded Piping. NUREG/CR-7015, BNL-NUREG -91346-2010.
  5. Park Y, DeGrassi G, Hofmayer C, Bezler P. Analysis of nuclear piping system seismic tests with conventional and energy absorbing supports. 14th International Conference on Structural Mechanics in Reactor Technology (SMiRT 14), Lyon, France. 2008.
  6. Cheung JH, Kim NS, Kim IT, Choi HS, Park CY, "KOCED Seismic Simulation Test Center" Journal of the Korean Society of Civil Engineers , 2009.Aug, Vol 57, No. 8, 43-49.
  7. ASME B, Pressure Vessel Code SectionXI. American Society of Mechanical Engineer. 2007.
  8. Choi HS, Cheung JH, Kim SH, Ahn JH. Structural Dynamic Displacement Vision System using Digital Image Processing. NDT & E International. 2011 Jun;44(7):597-608. https://doi.org/10.1016/j.ndteint.2011.06.003
  9. MTS STEX Manual. University at Buffalo Job No. US1.17858, EQT.
  10. DeGrassi G, Nie J, Hofmayer C. Seismic Analysis of Large-Scale Piping Systems for the JNES-NUPEC Ultimate Strength Piping Test Program. NUREG/CR-6983, BNL-NUREG-81548-2008
  11. ASCE Standard. Seismic Analysis of Safety-Related Nuclear Structure and Commentary. ASCE 4-98. American Society of civil Engineers. 1999.
  12. ASCE. Seismic Analysis of Safety-Related Nuclear Structures and Commentary. ASCE Standard 4-98, 1999.
  13. Cho SG, Kim DK, GO SH. Effects of Excitation Level on the Dynamic Characteristics of Electrical Cabinets of Nuclear Power Plants. Journal of the Earthquake Engineering society of Korea. 2010 Jun;14(3):23-30. https://doi.org/10.5000/EESK.2010.14.3.023
  14. Cho SG, So GH. Analysis of Ecperimental Modal properties of an Electric Cabinet via a Forced Vibration Test using a shaker. Journal of the Earthquake Engineering society of Korea. 2011 Dec;15(6):11-18.
  15. ASME CODE Section III, Division I, Subsection NB. ASME standard. 2007.
  16. Chio SJ, Seo YD, Choi HS, Kim IT, Cheung JH. Loading Experiments of the damaged TP 316 Stainless Pipe. KSCE Conference of the Civil Engineering society of Korea. 2011:69-72.